In order to predict accurately the cost of producing methane from urban refuse, studies were initiated on the dewatering of the fermentor residue and the disposal of the residue from the system. Results of the research are reported under the following subject headings: fermentation system; rheological properties of reactor slurry; filterability of reactor effluent; residue dewatering--vacuum filtration; settleability of solids in the reactor effluent; settleability of sludges from centrate treatment; centrifugation of reactor effluent; leachate potential of dewatered reactor residue; calorific value of the reactor residue; residue incineration; the production of panelboards; caustic treatment of digester feed; and, treatment of filtrate--centrate. Appendixes A, B, D, and E are included; Appendix C, which includes computer programs and documentation, is bound separately as Volume II of this report. (JGB)

Information is presented on: the concepts of flowability of bulk solids and of channels and the flow-no flow postulate; equipment and procedures for testing the flow of bulk solids; and bulk flow equipment design. This information should be sufficient to enable the engineer to design storage plants and flow channels for unobstructed bulk flow. Only an outline of the theory of flow is included. (LCL)

In FY-76, Task 3 of Contract E(04-3)-893 consisted of the following programs: fuel rod chemistry and thermodynamics; fuel rod engineering; fuel irradiations testing and analysis; and reference structural materials. Starting in FY-77, the Fuel Rod Engineering Program was reorganized into other existing G.E. programs under the E(04-3)-893 contract. Continuation of the reports on technical progress of this program can be found under 189 No. SG009, Task 3, or 189 No. SG023, Task 11.

The National Center for Analysis of Energy Systems at Brookhaven has been in operation since January 1976. This first annual highlights report outlines the scope of activities of the Center involving the integrated analyses of technological, economic, environmental, and social aspects of energy at the regional, national, and international levels. The objectives of the Center and major accomplishments of 1976 are described along with a list of active projects and publications. The energy data bases and analytical models used in the course of policy analyses are also described. The major ongoing activities of the Center include: long-range forecasting of energy-economic relationships; regional energy and environmental policy; comparative health effects of alternative energy systems; technology assessment and energy R and D priorities; development of energy-economic environmental models and data bases; R and D strategies for International Energy Agency; and energy technologies for developing countries.

Photograph used for a story in the Oklahoma Times newspaper. Caption: "Gregg Cloud right, discusses recently awarded scholarship with Yukon High School basketball coach Leroy Estes."

This report presents the results of the second-year effort within a three-year research project to develop a transportation planning methodology for small urban areas concerned with the provision of public transportation service. This phase of the research concentrates on problems of access to health services, transportation service for the disadvantaged, potential coordination and integration of existing transportation systems, alternative systems designs and their evaluation, and suitable marketing and monitoring programs for public transportation service in small urban areas. This effort, together with elements of the first-year research will culminate in the preparation of a transit planning manual suitable for use by the transportation planner in small to medium-size urban areas.

The model high-level waste solidification facility (WSF) is envisaged as being similar to the New Waste Calcining Facility (NWCF) being constructed at the Idaho National Engineering Laboratory but with provisions for incorporating the calcine into a glass. The decontamination factor (DF) is estimated to be one for tritium, 100 for iodine, and 5.0 x 10/sup 8/ for ruthenium. The DFs for other nuclides are in the range of mid to high 10/sup 9/. The volatile radionuclide of primary concern in waste solidification is ruthenium (in particular, /sup 106/Ru). With an estimated DF of 5.0 x 10/sup 8/, the /sup 106/Ru expected to be released from the WSF amounts to 3.4, 2.9, and 0.091 mCi/day for immediate solidification, a freshly filled waste tank (189 days), and five years of tank storage, respectively. The FSAR of the Barnwell Nuclear Fuel Plant Separations Facility implies that 4.6 mCi/day of /sup 106/Ru might be released from the stack of the separations facility and states that such a release meets all state and Federal standards and specifications.

One preserved mussel specimen including both the left and right valves. The specimen exhibits an oval shape; thin shell; double looped beak sculpturing; white internal coloring; tan external coloring; no external sculpturing. Collected in the San Jacinto basin. The specimen measures between 100 - 120 mm in length and was assessed to be recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a rhomboidal shape; thin shell; double looped beak sculpturing; bluish-white internal coloring; tan external coloring; no external sculpturing. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be long dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits an elliptical shape; thin shell; double looped beak sculpturing; bluish-white internal coloring; brown external coloring; no external sculpturing. The specimen measures between 0 - 60 mm in length and was assessed to be recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a round shape; moderately thick shell; white internal coloring; brown external coloring; external sculpturing in the form of pustules. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be relatively-recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a round shape; moderately thick shell; white internal coloring; brown external coloring; external sculpturing in the form of pustules. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a round shape; moderately thick shell; white internal coloring; brown external coloring; external sculpturing in the form of pustules. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be relatively-recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a round shape; moderately thick shell; white internal coloring; brown external coloring; external sculpturing in the form of pustules. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a round shape; moderately thick shell; white internal coloring; brown external coloring; external sculpturing in the form of pustules. Collected in the San Jacinto basin. The specimen measures between 0 - 60 mm in length and was assessed to be recently dead when collected.

One preserved mussel specimen including both the left and right valves. The specimen exhibits a rhomboidal shape; thin shell; double looped beak sculpturing; white internal coloring; tan external coloring; no external sculpturing. Collected in the San Jacinto basin. The specimen measures between 60 - 100 mm in length and was assessed to be recently dead when collected.

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Oklahoma County Associate district judge Gar C. Graham was one telephone call away from spending the night in the county jail Monday after being citied for direct contempt of court."

Photograph used for a story in the Oklahoma Times newspaper. Caption: "Joe Brown, a worker in the Oklahoma City-County Health Department, is one of those testing water samples for mercury content."

The Hawaii Geothermal Project, a coordinated research effort of the University of Hawaii, funded by the County and State of Hawaii, and ERDA, was initiated in 1973 in an effort to identify, generate, and use geothermal energy on the Big Island of Hawaii. A number of stages are involved in developing geothermal power resources: exploration, test drilling, production testing, field development, power plant and powerline construction, and full-scale production. Phase I of the Project, which began in the summer of 1973, involved conducting exploratory surveys, developing analytical models for interpretation of geophysical results, conducting studies on energy recovery from hot brine, and examining the legal and economic implications of developing geothermal resources in the state. Phase II of the Project, initiated in the summer of 1975, centers on drilling an exploratory research well on the Island of Hawaii, but also continues operational support for the geophysical, engineering, and socioeconomic activities delineated above. The project to date is between the test drilling and production testing phase. The purpose of this assessment is to describe the activities and potential impacts associated with extensive well flow testing to be completed during Phase II.

The background, capabilities and experience of the Garrett Corp. in designing, developing, manufacturing and testing gas turbines and related systems are described, and the requirements for and components of the Brayton Isotope Power System (BIPS) for space vehicles are outlined. Data on the compressor and turbine, alternator, bearings, recuperator, radiator, heat source assembly, and control systems are presented. (LCL)

Semi-weekly newspaper from Clarksville, Texas that includes local, state, and national news along with advertising.

Recent dipole-dipole resistivity surveys using 100 m and 300 m dipoles at Roosevelt Hot Springs KGRA, near Milford, Utah have suggested that the north-south length of the convective hydrothermal system may be as great as 20 km. Tertiary granite of the Mineral Mountain pluton seems to be intensely fractured along a narrow (500 m.) sinuous zone trending north and coinciding in part with the Dome Fault. This north-south fracture zone is crosscut by numerous east-west and some northwest-southeast faults. The brine in the fractures and alternation of feldspars to clay both result in lowered resistivities. Leakage of brine westward from the Dome Fault fracture zone is still a realistic interpretation of low resistivity values several kilometers west of the Dome Fault.

A simulated HCDA loading was applied in simple, thick-walled and thin-walled, 1/30-scale models of a fast breeder reactor vessel. The loading and resulting vessel response were measured to verify the modeling techniques used in the REXCO computer code. The sodium coolant is simulated by water, and the HCDA load is simulated by the expansion of the detonation products of a low-density explosive detonated in the vessel core. The detonation products expand from an initial pressure of 3700 psi down to 360 psi for a volume change of 410 cm/sup 3/, equal to the cover gas volume. The expansion produces 2.87 kW-sec of gas work up to slug impact on the vessel cover. From the strain measurements and the posttest deformation profiles of the vessel, the strain energy absorbed by the vessel before and after slug impact is calculated.

A limited time/funding study was performed to extrapolate the knowledge gained during the 127,000 gpm LSBR cold leg pump study to a 77,000 gpm hot leg pump application. Two conceptual designs are presented with the recommendation that the spherical casing diffuser pump, with an inducer/impeller, be used as the preferred design. However, further analysis is required to verify the acceptability of this concept for the specified thermal transients. The alternate design, which is heavier, larger, and more costly, would meet all thermal transient requirements, based on the extensive analysis and experience with the FFTF pump. For either hydraulic concept, an expeditious development effort is recommended to verify the inducer/impeller design.